LOCA frequency evaluation using expert elicitation-Reference-Cited by-同舟云学术

LOCA frequency evaluation using expert elicitation

Published:2007-07 Issue:12-13 Volume:237 Page:1429-1436
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Tregoning Robert Lee,Abramson Lee Richard,Scott Paul Michael,Chokshi Nilesh

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference7 articles.

1. An Introduction to the Bootstrap;Efron,1993

2. Rates of initiating events at U.S. nuclear power plants: 1987–1995;Poloski;NUREG/CR-5750,1999

3. U.S. Nuclear Regulatory Commission, 1990. Severe accident risks: an assessment for five U.S. nuclear power plants, NUREG-1150.

4. U.S. Nuclear Regulatory Commission, 1997. A pilot application of risk-informed methods to establish inservice inspection priorities for nuclear components at Surry unit 1 nuclear power station, NUREG/CR-1681, Rev.1, PNNL-9020, Rev.1.

5. U.S. Nuclear Regulatory Commission, 1999. Technical Elements of Risk-Informed Inservice Inspection Programs for Piping, Draft Report, NUREG-1661.

Cited by 4 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. ATHLET Simulation of PKL I2.2 IB-LOCA Benchmark Test and Quantitative Assessment;Nuclear Technology;2022-02-10

2. Optimization of the Nodalization of Nuclear System Thermal-Hydraulic Code Applied on Primary Loop Benchmark;Journal of Nuclear Engineering and Radiation Science;2021-10-19

3. Sensitivity analysis of thermal-hydraulic models based on FFTBM-MSM two-layer method for PKL IBLOCA experiment;Annals of Nuclear Energy;2020-11

4. Post-test thermal-hydraulic analysis of two intermediate LOCA tests at the ROSA facility including uncertainty evaluation;Nuclear Engineering and Design;2013-11